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| Report | FZJ-2016-06203 |
; ; ;
2009
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag
Jülich
Please use a persistent id in citations: http://hdl.handle.net/2128/12801
Report No.: Juel-4294
Abstract: The TINTE main documentation consists of three parts, the first two of which/1/,/2/ have been published (in German) in the late eighties. In the first part the problems of modelling the nuclear and thermo-gas-dynamic behaviour of the primary circuit of a high temperature gas cooled reactor (HTGR) have been discussed in detail. It has been explained how the multiconnected system can be decomposed into single tasks to be solved separately. The solution of the total system is thus found by iteration of the partial results. In the second part of the documentation some major applications of TINTE are demonstrated. Among them the analyses of dynamic reactor experiments performed at the AVR reactor /4/ are of special interest. These results play a major role in the TINTE validation process, and the very good conformance obtained with the experimental data validate the TINTE calculations to a considerable extent. Earlier post-calculations of the AVR experiments with a previous version of the TINTE code have been described in /5/. Moreover, the basic algorithms as used in TINTE together with some applications have been shown in /4/. Since not all of the capabilities of TINTE could be addressed in these analysis, the validation process was continued, e.g. with the evaluation of the VELUNA corrosion experiments /6/. An addendum to the principal considerations of /1/ has been added as a supplement to /2/. Here the gas flow in an optional 1-D component and flow network is described, which may be used to enhance the 2-D reactor model for special situations. This flow network was necessary to model non-central pipes and other three-dimensional gas flow paths. It allows the description of co-axial pipes and a lumped parameter simulation of the primary side ofheat exchangers or steam generators. One example in /4/ shows that under certain limitations even a simulation of a gas-gas heat exchanger and the incorporation of the secondary loop is possible with the aid of that flow-network. In this addendum the possibility is also introduced to calculate the pressure inside the reactorfrom a given (fixed or variable in time) gas inventory. This is of relevance for accident analyses, where a failure of the pressure enclosure is assumed. If the pressure increases significantly gas may be removed from the system by burst discs or safety valves. This document starts with a description of the TINTE code structure (Section 4), while Section 5 is dedicated to the description and interpretation of the main input data. Section 6 deals with the preparation of the nuclear data base, the generation of the cross-section polynomial expansions and the necessary interface codes. Aspects included here are the evaluation of nuclide vectors (prepared by burn-up codes) and the preparation of spectrum calculations with variation of temperatures, buckling and concentrations for spectrum relevant nuclides. User notes on the code installation and calculational procedures are presented in Section 7, while Sections 8 and 9 discuss the TINTE control options and output data options, respectively. Section 10 lists the changes made in the TINTE source code over the years. The report also includes in the Appendices some newer algorithms for the treatment of special situations, while a description of the correlations used for the heat capacities and thermal conductivities are also given. Of special note here is Appendix E, which lists the detail of the ROMO model newly implemented in TINTE in 2004.
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